Advancement of elemental analytical model in LEAP-III code for tube failure propagation

If pressurized water or its vapor leaks from a ruptured heat transfer tube in a steam generator of a sodium-cooled fast reactor, a high-velocity, high-temperature, and corrosive jet with sodium-water chemical reaction may cause tube failure propagation. In this study, an analytical method was develo...

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Autores principales:	Akihiro UCHIBORI, Hideki YANAGISAWA, Takashi TAKATA, Jiazhi LI, Sunghyon JANG
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	sodium cooled fast reactor steam generator sodium water reaction tube failure propagation overheating rupture numerical analysis Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/5f8ef72c6563470798477dc7affd2e8b
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spelling	oai:doaj.org-article:5f8ef72c6563470798477dc7affd2e8b2021-11-29T05:56:30ZAdvancement of elemental analytical model in LEAP-III code for tube failure propagation2187-974510.1299/mej.19-00548https://doaj.org/article/5f8ef72c6563470798477dc7affd2e8b2020-03-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00548/_pdf/-char/enhttps://doaj.org/toc/2187-9745If pressurized water or its vapor leaks from a ruptured heat transfer tube in a steam generator of a sodium-cooled fast reactor, a high-velocity, high-temperature, and corrosive jet with sodium-water chemical reaction may cause tube failure propagation. In this study, an analytical method was developed to predict the occurrence of tube failure propagation by overheating rupture. This method consists of the elemental analytical models for a sodium-side temperature distribution formed by a reacting jet, water-side thermal hydraulics, heat transfer between a fluid and a tube, and tube failure by internal pressure. To evaluate the tube failure propagation in a short computation time, these models are based on the experimental data, semi-theoretical correlations, or one-dimensional equations. Applicability of the proposed method was investigated through the numerical analysis of an experiment on water vapor discharging into the liquid sodium. This analysis demonstrated that the method could predict the occurrence of overheating rupture and provide conservative results. While the proposed method is useful for high-speed computations, this method evaluates a high temperature region with a large conservativeness in some cases. To improve this conservativeness, a Lagrangian particle model for the reacting jet was also developed as an alternative method. The numerical analysis by this model showed that the discharged gaseous particles spread with particle-particle and particle-tube interactions.Akihiro UCHIBORIHideki YANAGISAWATakashi TAKATAJiazhi LISunghyon JANGThe Japan Society of Mechanical Engineersarticlesodium cooled fast reactorsteam generatorsodium water reactiontube failure propagationoverheating rupturenumerical analysisMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00548-19-00548 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	sodium cooled fast reactor steam generator sodium water reaction tube failure propagation overheating rupture numerical analysis Mechanical engineering and machinery TJ1-1570
spellingShingle	sodium cooled fast reactor steam generator sodium water reaction tube failure propagation overheating rupture numerical analysis Mechanical engineering and machinery TJ1-1570 Akihiro UCHIBORI Hideki YANAGISAWA Takashi TAKATA Jiazhi LI Sunghyon JANG Advancement of elemental analytical model in LEAP-III code for tube failure propagation
description	If pressurized water or its vapor leaks from a ruptured heat transfer tube in a steam generator of a sodium-cooled fast reactor, a high-velocity, high-temperature, and corrosive jet with sodium-water chemical reaction may cause tube failure propagation. In this study, an analytical method was developed to predict the occurrence of tube failure propagation by overheating rupture. This method consists of the elemental analytical models for a sodium-side temperature distribution formed by a reacting jet, water-side thermal hydraulics, heat transfer between a fluid and a tube, and tube failure by internal pressure. To evaluate the tube failure propagation in a short computation time, these models are based on the experimental data, semi-theoretical correlations, or one-dimensional equations. Applicability of the proposed method was investigated through the numerical analysis of an experiment on water vapor discharging into the liquid sodium. This analysis demonstrated that the method could predict the occurrence of overheating rupture and provide conservative results. While the proposed method is useful for high-speed computations, this method evaluates a high temperature region with a large conservativeness in some cases. To improve this conservativeness, a Lagrangian particle model for the reacting jet was also developed as an alternative method. The numerical analysis by this model showed that the discharged gaseous particles spread with particle-particle and particle-tube interactions.
format	article
author	Akihiro UCHIBORI Hideki YANAGISAWA Takashi TAKATA Jiazhi LI Sunghyon JANG
author_facet	Akihiro UCHIBORI Hideki YANAGISAWA Takashi TAKATA Jiazhi LI Sunghyon JANG
author_sort	Akihiro UCHIBORI
title	Advancement of elemental analytical model in LEAP-III code for tube failure propagation
title_short	Advancement of elemental analytical model in LEAP-III code for tube failure propagation
title_full	Advancement of elemental analytical model in LEAP-III code for tube failure propagation
title_fullStr	Advancement of elemental analytical model in LEAP-III code for tube failure propagation
title_full_unstemmed	Advancement of elemental analytical model in LEAP-III code for tube failure propagation
title_sort	advancement of elemental analytical model in leap-iii code for tube failure propagation
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/5f8ef72c6563470798477dc7affd2e8b
work_keys_str_mv	AT akihirouchibori advancementofelementalanalyticalmodelinleapiiicodefortubefailurepropagation AT hidekiyanagisawa advancementofelementalanalyticalmodelinleapiiicodefortubefailurepropagation AT takashitakata advancementofelementalanalyticalmodelinleapiiicodefortubefailurepropagation AT jiazhili advancementofelementalanalyticalmodelinleapiiicodefortubefailurepropagation AT sunghyonjang advancementofelementalanalyticalmodelinleapiiicodefortubefailurepropagation
_version_	1718407586897723392

Advancement of elemental analytical model in LEAP-III code for tube failure propagation

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